Experimental study on the natural circulation of a passive residual heat removal system for an integral reactor following a safety related event |
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Authors: | Hyun-Sik Park Ki-Yong ChoiSeok Cho Sung-Jae YiChoon-Kyung Park Moon-Ki Chung |
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Affiliation: | Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of Korea |
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Abstract: | Natural circulation characteristics of an integral type reactor during the operation of a passive residual heat removal system (PRHRS) following a safety related event has been experimentally investigated by using the VISTA facility. A PRHRS actuation trip signal is generated by a high power trip signal following a steam flow increasing event. The experimental results show that the single-phase coolant flows steadily in the primary loop by a natural convection process and that it effectively removes the decay heat from the core through a steam generator during the PRHRS operation. The heat transfers through the PRHRS heat exchanger and the emergency cooldown tank (ECT) are sufficient enough to enable a two-phase natural circulation of the coolant in the PRHRS loop. |
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